ML20129F819

Rev 0 to SG Replacement Rept

ML20129F819
Person / Time
Site:	Point Beach
Issue date:	09/26/1996
From:	WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML19355E414	List: ML20129F793 ML20129F819 ML20129F824 ML20129F843
References
PBNP-IC-25, PBNP-IC-25-R, PBNP-IC-25-R00, NUDOCS 9610020099
Download: ML20129F819 (15)

Text

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j POINT BEACH NUCLEAR PLANT UNIT 2 STEAM GENERATOR REPLACEMENT PROJECT l

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STEAM GENERATOR l

REPLACEMENT REPORT I

(

ATTACHMENT b SHT Il._d.

~

CALC NO.:

PENP-3C-25

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9610020099 960926 PDR ADOCK 05000266 P

PDR h

s REVEW AND APPROVAL RECORD

' PLANT Point Beach Nuclear Plant UNIT 2

PROJECT Steam Generator Replacement Project DOCUMENT TITLE Steam Generator Replacement Report REVISION NO.

O REVIEW AND APPROVAL:

GROUP INTERFACE TYPE PREPARED BY/

REVIEWED /

DATE VERIFIED BY/

INPUT REVIEW N/A DATE CW1 X

MECH X

ELECT x

LICN X

ALARA X

SP PROC X

-CEM X

OVERALL APPROVAL BY:

DATE:

~

~~'

Design Engineenng/ Licensing Manager l

bSHTk_

ATTACHMENT CALC NO.:

~

f?bNP - TC-26 l

l Form ;E? 7 2-1. 09,15-95

he The RSG tube bundle 4 ddgacd to holmore U-tubes than the OSG tube bundle (3499 versus l

3260), and hence a greater heat transfer surface area (47,500 versus 44,300 square feet) and cross flow area. These features provide greater heat transfer and a slight increase in best estimate primary flow rates to enhance thermal performance. This, in turn, offsets the reduction in material thermal conductivity from RSG use of thermally treated Alloy 690, as compared to mill annealed Alloy 600 used in the OSG tubing.

3.2.3 Material Comparison Materials used in the fabrication of the RSGs are equivalent to those used in the OSGs, with the following notable exceptions, diced $dM These material changes do not compromise the performance of the RSGs.

fa The shell barrels plate material has' changed from ASME S A-302, Grade B to ASME SA-533 Type B, Class 2.

The transition cone material has been changed from ASTM A-283 seam welded plate to ASME SA-508, Class 3 hollow forgings.

The elliptical head material has been changed from ASME SA-302, Grade B plate to AShE SA-508, Class 3a forging.

The tube plate forging material has been changed from ASNE SA-336 to AShE SA-508, j

Class 3a.

The tube support plate material has been changed from ASME SA-285, Grade C to ASME S A-240, Type 405.

The steam generator tubing material has been changed from ASNE SB-163 Alloy 600 to ASNE SB-163 Alloy Tube Set 690 (Code Case N-20-1).

The AVB ' material has been changed from SB-166 Alloy 600 with chromium plating to A-479 Type 405 stainless steel. AVB ends will have thermally treated SB-167 Alloy 690 end i

caps secured to SB-166 Alloy 690 retaining rings.

ATTACHMEr,7 b 9 T.)...)._

CALC NO.:

libhiP - TC - Zh Point Beach Unit 2 SGRR Page 3-5 Draft Rev 0 III22/95

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q-l FACSIMILE

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DATE:

MAY 5, 1994 TO:

VECTRA TECHNOLOGIES, INC.

1330 BUTTERFIELD ROAD SUITE 550 DOWNERS GROVE, IL. 60515 KAREN DEPODASTA FAX # 708-512-8660 PHONE # 708-512-8659 FROM:

THE FOXBORO COMPANY 1

33 COMMERCIAL STREET D.3347/B52-2K FOXBORO, MA. 02035 I

DAVID R. RINGLAND FAX # 508-549-6580 PHONE # 508-549-6333 FILE:

VECTRA - CABCULATION,INFORMATION FOR N-E10 SERIES.

TRANSKITTERS.

SUBJECT:

YOUR-FACSIMILE TO OUR MR. F. BONFANTI, DATED MARCR'29p 1994.

PAGES:

THREE INCLUDING THIS PAGE.

COPIES:

F. BONFANTI, CH1-01 R. SCHWANTIES CH1-01 0

l0 SHT I-ATTACHMENT CALC N04 7gp(P- $ 0- b l

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sa.ca..=ceu e.

ResDonses to Questions from Vectra' Recaidine N-E11 and N-E13 Transmitters

References:

PSS9-1BlA (1984)

)

and FOXBORO Qualification Document QOAAC11 i

1. Accuracy expressed as a +/- % does include the combined i

Each of the aforementioned characteristics has a specifiede i

limit.

specification. All specification are in 4 of Span.The specified limit

2. The performance characteristics in Question / Response 1.

are measured at " Reference Operating Conditions" and performance at " Normal Operating Conditions" includes the influences of Ambient Temperature Effects, Accuracy under ambient temperature changes does affect etc.

the zero and span of the transmitter. The other characteristics should not change, but are not specified at other than reference operating conditions.

Using the example of an N-E11DM transmitter the Ambient Temperature Effects are specified as follows:

Zero Shift Span Settings,% of USL per 100F Change,% of Span Above lipj_oq 132 to 180F)

_(80 to 250F) per 170F Change 80%

100%

+/-1%

+/-2%

50%

80%

+/-1.5%

+/-3%

20%

50%

+/-2.5%

+/-S%

Span Change: +/-1.25% per 100F Example:

N-E11DM-IIB, Calibrated Range: 0-100 psi USL:200 psi 100 psi = 50% of USL 200 psi therefore the Ambient Temperature Effects are :

+/-2.5%/100F or +/-5%/170F Relative Humidity Effects: Negligible (N-Ell and N-E13 Transmitters are sealed for DBE of LOCA/HELB to 85 psi, thus humidity has no effect.)

3. The " Normal R TID of 3.5x10gdiation" Specification of +/-0.5% for a specification. FOXBORO Qualification Report QOAAC11, rads gamma is i Sect.IV., Pg. IV-25 does show graphically several other lower radiation levels for an N-E11GM transmitter which is similar to an N-E11DH transmitter. The radiation effects can be zero and span adjusted to return to the normal accuracy specification.

ATTACHMENT ___. O ' g j 7)

CALC N04 fWP'Y& Y

rp-05-1994 13:53 FRCy1 PUR1MJ3 6,q_Es TO 87085128660 P.03

4. The Seismic DBE performance specifications of +/-S% Duri were set as goals in the transmitter qualification ng and we did not attempt to determine a threshold response spectrum. Reviewing the qualification data for the similar transmitter an N-E11GM (F1) it is possible that spans above this setting do havewhose span s

USL, better performance specifications.

S. The LOCA/HELB output Shifts of +/-8% at 25% of these limits. Using the N-E11GM from the een the span setting was 40% of USL thus the + qualification test be selected.

/-8% spec. would the 50 to 80% span settings can be developed:Using the Am i

Span Settings, output Shift, Span

• Output Shift,

% of USL

% of Span Setting

% of Span Above IToto ist 3 Hrs.

Ratio 50 to 80%

80%

100%

+/-3%

Ref.

50%

80%

1.5

+/- 4. 5 %

20%

50%

+/-at 2.5 Adding margin we would specify the output Shift at +/-S% for the 50 to 80% of USL settings.

• The LOCA/HELB is an event similar to ambient temperature effects and the use of the normal ambient temperature specifications is justified in deriving an error ratio for the 50 to 80% settings and applied to the USL specification.

Note:

The N-E11GM and N-E11DH transmitters have the same Ambient Temperature Effects as stated above, other N-E10 Series Transmitters the manner of for specification differs and must be reviewed individually.

C# 3" ATTAUdM M CALC NO pjbdF-$U b TOTA P.01

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~-CM E<>- srtC5 D M4*.422:2013 pp2, et,g l

• • PRELIMINAR.Y**

D*liverables, 1.

Tables for each PMA tam. calculated.

)

2.

Tables for CENCODE inputs to the PMA calculations (limited to bounding uprated conditions.;

3.

'SG PMA Customer notificatica letter 4.

Sae.ple calculation demonstrating :nethod of the calculations.

1 j

l

.r'*

Post-it' Fax Note 7671

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ATTACHMENT SH CALC N04 ybhfP *CC-75

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4. -cc.,. 's f'. U4

, y 22 '96 09:50 N15ca sPc46 70 3:41.t2212010 peca.m.s t

1

• PRELIMDuutY *

• i Act.tch:nent A

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Table 3 l

set

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poa.st ___.

I

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tow tespeins l

l Process l Unit 1 44F Unit 1 44F bait 1 44F Unit 2 447 j

^{Measurement I Current Tap Carrent Tsp Relocat<d Tap Uprated I

Allowance Current Power Uprated Power Uprated Power Power I

i.

Process

+ 0.00061

- 0.048%

+ 0.23566

+ o.2355%

)

Pressure High

\\

l f Process

+ 0.1662)

+ 0.1662%

.- 0.2852t

- 0.2852%

Pressure Low Fluid Velocity Effects 0.2424

- 0.242) 2.04234

1. 636cT t Downcon:mer 1.18114

+ 0.7376%

+ 1.31894

+

+ 1.3906 Subcooling I

{

f combtned l Velocity and

,! + 0.939%

0.4956)

- 0.7235g

- o.2462t

+

l subcooling l

e :ects Notes:

1, All values are in percent of instrument water Icvol span.

2.

Unis 2 a47 steam Generators at uprated conditions bounds current power level ope ra ti.on.

3.

With the current tap location setpoint is 20% Narrev Range Span for Unit 1.

Relocated Span is calculated at 30% Narrow Range Span.

ATTACHMENT ) SHT23 l

CALC NO.:

TbNP-TC-36

rcr-e r nrrge m.,www..o v.ty x g :ir::v m

A'.

• encc....V

r. d

, ALII 22 ' % 29:54

-W 1 Ecw SPEC ~m.

70 3141422120 9 PcCE. Mee i

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• FREI.IM19tARY a

• J I

i 1

Attach:nent A i-Table 4 I

S*5Poiat l

1.ow - Low setpoint l Process

! Unit 1 44r Unit.1 44P Unit 1 44P Unic 2 447 P.easuronent

' Current Tap cessent Tap Relocated tsp Uprated

(

f

) Allowance Current Power Uprated Power Uprated Power Power I

F f Process

- 0.00174 0.1392%

' O.0945%

+ 0.0945%

~

l Pressure Eigh j

Process-

+ 0.39081

+ 0.3908%

- 0.06064

- 0.06066

(

Pressure Low Fluid VelocLty Effects

- 0.2315%

- 0.23151

-.1.91754

- 1.5505%

Downeoanner

+ 0.96384 6 0.606%

t 1.1255

+ 1.1854%

subcooling l

Combined i

velocity and

+ 0.7323%

' O.37456

- 0.792S4

- 0.36511 I

subcooling eifects i

Notes l

1.

All values are in percent of instrument water level span.

2.

Unit 2 447 Steam Generators at uprated conditions bounds current power level operation.

3.

Wit.h the current tap location setpoint is 20% Narrow Range Span for Unit 1.

Relocated span is calculated at 253 Narrow aange span.

ATTACHMENT M S.,T bi CALC No.:

1%NF-Tc-25 u TOTAL PACE.0CS =

. = - - - _ -

o.

l l

Revised FSAR Mark-up for the Steam Generator Tube Rupture Accident

J J

l TABLE 14.2.4-J

's.

THYROID DOSES AND WHOLE BODY DOSES STEAM GENERATOR TUBE RUPTURE ACCIDENT l

s wid au-ne:LtM p:. : : :" 9'-'

" ! "; 0 " ! ' t

":n

.::-d: :: _

A.

i 0 - 2 HOUR 0 - 6 HOUR DOSE AT SITE BOUNDARY 00SE AT LPZ THYR 01D M BODY THYROID f h BODY a

82 15.1

y. y' f.B

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36 5 0JM

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0. R.;*

+yppygra a

4/8 /'"_*k_!)=_N$& &._,, g, g,

u_

nu m

_.m

__2___---

_f_

g, 0 - 2 HOUR 0 - 6 HOUR l

4 DOSE AT SITE BOUNDARY DOSE AT LPZ s-r-

THYROIO Augur BODY BIBQ1Q meent 800Y 82 B2

3. (>

qy o.yy J67~

M1XW, M*

S oxte

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+vepute*

4dide

+eHwt**

1 TE:

1.

el Def t = 15 mary to onda sak e=.

G l

F J

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Technical Specifications Section 15.3.4 Basis 1

The PBNP FSAR Table 4.1-4 shows that the largest steam generator liquid volume is based on the Unit 1 Steam Generators. This volume (2877 ff = 81.5 m')is being used as the appropriate j

value for Basis of TS 15.3.4. The edited Technical Specifications page 15.3.4-3 is provided with j

this attachment.

i

I For the purposes of determining a maximum allowable secondary coolant activity, the steam break accident is based on a postulated release of the contents of one steam generator to the atmosphere using a site boundary dose limit. The limiting l

dose for this accident results from iodine in the secondary coolant.1-131 is the dominant isotope because ofits low MPC in air and because the other iodine isotopes have shorter half-lives and therefore cannot buildup to significant concentrations in the secondary coolant, given the limitations on primary system leak rate and activity. It is assumed that the accident occurs at zero load, yhich is when the maximum amount of water is contained in one steam generator. One tenth of the contained iodine is assumed to reach the site boundary, making allowance for plate-out and retention in water l

droplets. It is conservative to measure gross beta-gamma activity except when the gross activity exceeds or equals 1.2 pCi/cc. At this time the iodine-131 activity must be measured.

The maximum inhalation dose at the site boundary is then as follows:

j Dose (rem) = C x V x B(t)x x x DCF IO O

where:

C

= secondary coolant activity (1.2 Ci/cc = 1.2 Ci/m')

l V

= water volume in one steam generator (2824-2877 ff = 804 Lim')

j i

l B(t)

= breathing rate (3.47 x 10" m'/sec) x/Q

= 3.0 x 10" sec/m' W l

DCF

= 1.48 x 10' rem /Ci 1-131 inhaled The resultant dose is sligh!!y != th= approximatelv 1.5 rem.

References:

FSAR Section 10 FSAR Section 14 Unit 1 - Amendment Na IS.3.4-p IJnit 2 - AmendH ELNE

l Clarification of the Total Primary Heat Output Changing from 1518.5 MWt to 1524.5 MWt

]

The FSAR mark-up provided as an attachment to the previous supplement to Technical Specifications Change Request 188 and 189, dated August 5,1996, contained a change to identify the Total Primary lieat Output as 1524.5 MWt compared to the previous value of 1518.5 MWt listed in FSAR Table 4.1-4. It has been determined that this parameter should include the approximate amount of heat (thermal power) generated by the Reactor Coolant Pumps. This is approximately 6 MWt.

i

Non-proprietary Version of OTAT and OPAT Uncertainty Analysis with Affidavit l

in accordance with the requirements of 10 CFR 2.790 l

Enclosed are:

1.

5 copies of"Setpoint Methodology for Overtemperature - AT and Overpower - AT Reactor Protection Setpoints for Point Beach Units I and 2," dated March 1996 (Proprietary).

2.

5 copies of"Setpoint Methodology for Overtemperature - AT and Overpower - AT Reactor Protection Setpoints for Point Beach Units 1 and 2," dated March 1996 i

(Non-Proprietary).

Also enclosed are a' Westinghouse authorization letter, CAW-96f-1007 accompanying affidavit, Proprietary Information Notice, and Copyright Notice.

As Item I contains information proprietary to Westinghouse Electric Corporation, it is supported by an affidavit signed by Westinghouse, the owner of the information. The affidavit sets for the basis on which the information may be withheld from public disclosure by the Commission and addresses with specificity the considerations listed in paragraph (b)(4) of Section 2.790 of the Commission's regulations.

Accordingly, it is requested that the information which is proprietary to Westinghouse be withheld from public disclosure in accordance with 10 CFR 2.790.

Correspondence with respect to the copyright or proprietary aspects of the items listed above or the supporting Westinghouse Affidavit should reference CAW-96-1007 and should be addressed to N.J. Liparulo, Manager of Regulatory and Engineering Networks, Westinghouse Electric Corporation, P.O. Box Pittsburgh Pennsylvania 15230-0355.

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